Fusion Science and Technology / Volume 61 / Number 1T / January 2012 / Pages 293-297
Modeling and Simulations / Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems / dx.doi.org/10.13182/FST12-A13435
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The status of the development of a coupled neutronic/thermal-hydraulic model for the stability and safety analysis of advanced lead-cooled fast fission reactors is presented.